Pressure vessel lead factor determination method and device, electronic equipment and storage medium

Abstract

The embodiment of the invention provides a pressure vessel lead factor determination method and device, electronic equipment and a storage medium, and belongs to the technical field of nuclear reactors. The method comprises the following steps: acquiring first relative power of a first fuel assembly in a first reactor and second relative power of a second fuel assembly in the first reactor; determining a first contribution share of the first fuel assembly to the fast neutron fluence at the neutron detector in the irradiation monitoring pipe, and determining a second contribution share of the second fuel assembly to the fast neutron fluence at the fluence peak position of the pressure vessel; and determining the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share and the second contribution share. The embodiment of the invention can reduce the calculation cost of the lead factor.

Description

Technical Field

[0001] The present application relates to the field of nuclear reactor technology, and in particular to a method, device, electronic equipment and storage medium for determining an advance factor of a pressure vessel. Background Art

[0002] The Reactor Pressure Vessel (RPV) is the main pressure-bearing equipment of a nuclear reactor. It is the second safety barrier to prevent radioactive proliferation and the primary circuit pressure boundary. It cannot be replaced during the life of the reactor and plays a vital role in the safety and life of the nuclear power plant.

[0003] The irradiation monitoring tube is a device used to monitor and predict the material changes of the reactor pressure vessel after being irradiated by neutrons. Since the irradiation monitoring tube is close to the core, it is subjected to stronger neutron irradiation than the pressure vessel, so it can predict the degree of irradiation damage to the pressure vessel material. During the designed service life of the reactor, the irradiation monitoring tube can be withdrawn as planned during the shutdown and refueling period. By testing and analyzing the irradiation monitoring tube, the material degradation tendency of the reactor pressure vessel can be determined.

[0004] The lead factor characterizes the ratio of the fast neutron flux at the neutron detector in the irradiation monitoring tube to the maximum fast neutron flux at the inner surface and 1 / 4 thickness of the pressure vessel, and is an important basis for nuclear power plants to formulate irradiation monitoring programs. Based on the lead factor, the time to raise the irradiation monitoring tube can be determined.

[0005] At present, it is usually necessary to establish a particle transport model for a large-scale reactor and perform calculations on the particle transport model to obtain the lead factor. In this process, a large amount of computing resources and computing time are required, and there is a problem of high computing cost. Summary of the invention

[0006] The main purpose of the embodiments of the present application is to propose a method, device, electronic device and storage medium for determining an advance factor of a pressure vessel, aiming to reduce the calculation cost of the advance factor.

[0007] To achieve the above-mentioned purpose, a first aspect of an embodiment of the present application provides a method for determining an advance factor of a pressure vessel, the method comprising:

[0008] Obtaining a first relative power of a first fuel assembly in a first reactor and a second relative power of a second fuel assembly in the first reactor, wherein the first fuel assembly is a fuel assembly whose distance from an irradiation monitoring tube is less than a first preset value, and the second fuel assembly is a fuel assembly whose distance from a pressure vessel is less than a second preset value;

[0009] Determining a first contribution share of the first fuel assembly to the fast neutron flux at a neutron detector in the irradiation monitoring tube, and determining a second contribution share of the second fuel assembly to the fast neutron flux at a peak position of the flux of the pressure vessel;

[0010] An advance factor of the pressure vessel is determined according to the first relative power, the second relative power, the first contribution share, and the second contribution share.

[0011] To achieve the above-mentioned purpose, a second aspect of an embodiment of the present application provides a pressure vessel lead factor determination device, the device comprising:

[0012] a power acquisition module, used for acquiring a first relative power of a first fuel assembly in a first reactor, and a second relative power of a second fuel assembly in the first reactor, wherein the first fuel assembly is a fuel assembly whose distance from an irradiation monitoring tube is less than a first preset value, and the second fuel assembly is a fuel assembly whose distance from a pressure vessel is less than a second preset value;

[0013] a share determination module, configured to determine a first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and to determine a second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel;

[0014] An advance factor determination module is used to determine the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share, and the second contribution share.

[0015] To achieve the above-mentioned purpose, the third aspect of an embodiment of the present application proposes an electronic device, which includes a memory and a processor, the memory stores a computer program, and when the processor executes the computer program, it implements the method for determining the lead factor of a pressure vessel described in the first aspect.

[0016] To achieve the above-mentioned purpose, the fourth aspect of an embodiment of the present application proposes a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, it implements the method for determining the lead factor of a pressure vessel described in the first aspect above.

[0017] To achieve the above-mentioned purpose, the fifth aspect of an embodiment of the present application proposes a computer program product. When the instructions in the computer program product are executed by a processor of an electronic device as described in the third aspect, the electronic device executes the method for determining the lead factor of a pressure vessel as described in the first aspect above.

[0018] The method, device, electronic device and storage medium for determining the lead factor of a pressure vessel proposed in the present application obtain the first relative power of the first fuel assembly in the first reactor and the second relative power of the second fuel assembly in the first reactor, and determine the first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and determine the second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel, and then determine the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share and the second contribution share. Through the above steps, according to the first relative power, the second relative power, the first contribution share and the second contribution share of the first reactor, the lead factor of the pressure vessel in the first reactor can be determined simply and quickly, reducing the calculation cost of the lead factor. BRIEF DESCRIPTION OF THE DRAWINGS

[0019] Figure 1 is a flow chart of a method for determining an advance factor of a pressure vessel provided in an embodiment of the present application;

[0020] Figure 2 is another flow chart of the method for determining the lead factor of a pressure vessel provided in an embodiment of the present application;

[0021] Figure 3 is a schematic structural diagram of a pressure vessel lead factor determination device provided in an embodiment of the present application;

[0022] Figure 4 It is a schematic diagram of the hardware structure of the electronic device provided in the embodiment of the present application. DETAILED DESCRIPTION

[0023] In order to make the purpose, technical solution and advantages of the present application more clearly understood, the present application is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and are not used to limit the present application.

[0024] It should be noted that, although the functional modules are divided in the device schematic diagram and the logical order is shown in the flowchart, in some cases, the steps shown or described may be performed in a different order than the module division in the device or the order in the flowchart. The terms "first", "second", etc. in the specification, claims and the above drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence.

[0025] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by those skilled in the art to which this application belongs. The terms used herein are only for the purpose of describing the embodiments of this application and are not intended to limit this application.

[0026] First, some nouns involved in this application are analyzed:

[0027] Reactor: A device that can convert nuclear energy into heat or other forms of energy by precisely controlling the speed and scale of nuclear fission reactions. It is usually composed of a core, coolant system, moderator system, control and protection system, shielding system, radiation monitoring system, etc.

[0028] Core: The core component of a reactor, used to generate the required heat source. The core consists of multiple fuel assemblies arranged in a certain order and spacing. Multiple fuel assemblies can be used to load nuclear fuel and produce nuclear fission to generate heat.

[0029] Irradiation monitoring tube: a component used to monitor and predict the changes in the material of the pressure vessel after irradiation. During the life of the reactor, the irradiation monitoring tube is taken out periodically and performance tests and analysis are carried out to obtain the material degradation trend of the reactor pressure vessel.

[0030] Pressure vessel: A closed container used to house the reactor and withstand the operating pressure of the reactor. The pressure vessel can form a pressure boundary for the high-pressure coolant together with the primary circuit pipeline, ensuring that the fission reaction of the nuclear fuel is carried out in a safe and sealed space.

[0031] In order to solve the problems of the prior art, an embodiment of the present application provides a method, device, electronic device and storage medium for determining an advance factor of a pressure vessel, which is specifically illustrated by the following embodiments. First, the method for determining the advance factor of a pressure vessel in an embodiment of the present application is described.

[0032] The method for determining the lead factor of a pressure vessel provided in the embodiment of the present application relates to the field of nuclear reactor technology. The method for determining the lead factor of a pressure vessel provided in the embodiment of the present application can be applied to a terminal, can be applied to a server side, or can be software running in a terminal or a server side. In some embodiments, the terminal can be a smart phone, a tablet computer, a laptop computer, a desktop computer, etc.; the server side can be configured as an independent physical server, or can be configured as a server cluster or a distributed system composed of multiple physical servers, or can be configured as a cloud server that provides basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communications, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the method for determining the lead factor of a pressure vessel, etc., but is not limited to the above forms.

[0033] The present application can be used in many general or special computer system environments or configurations. For example: personal computers, server computers, handheld or portable devices, tablet devices, multiprocessor systems, microprocessor-based systems, set-top boxes, programmable consumer electronics, network PCs, minicomputers, mainframe computers, distributed computing environments including any of the above systems or devices, etc. The present application can be described in the general context of computer-executable instructions executed by a computer, such as program modules. Generally, program modules include routines, programs, objects, components, data structures, etc. that perform specific tasks or implement specific abstract data types. The present application can also be practiced in distributed computing environments, in which tasks are performed by remote processing devices connected through a communication network. In a distributed computing environment, program modules can be located in local and remote computer storage media including storage devices.

[0034] Figure 1 is a flow chart of a method for determining an advance factor of a pressure vessel provided in an embodiment of the present application, Figure 1 The method may include but is not limited to steps 101 to 103.

[0035] Step 101, obtaining a first relative power of a first fuel assembly in a first reactor and a second relative power of a second fuel assembly in the first reactor, wherein the first fuel assembly is a fuel assembly whose distance from an irradiation monitoring tube is less than a first preset value, and the second fuel assembly is a fuel assembly whose distance from a pressure vessel is less than a second preset value.

[0036] The first reactor is a reactor for which the lead factor of the pressure vessel needs to be determined, and includes a core, a power measurement device, an irradiation monitoring tube and a pressure vessel. For the first reactor in operation, the radial power distribution of the first reactor can be measured by the power measurement device. For the first reactor in non-operation, the radial power distribution can be determined according to the design value in the core fuel management plan of the first reactor.

[0037] The core includes a plurality of fuel assemblies, and the plurality of fuel assemblies include a first fuel assembly, a second fuel assembly, and other fuel assemblies. Among them, the first fuel assembly is an m-group fuel assembly whose distance from the irradiation monitoring tube is less than a first preset value. The second fuel assembly is an n-group fuel assembly whose distance from the pressure vessel is less than a second preset value. Specifically, m and n are both integers greater than or equal to 1, and m and n can take the same value or different values. Generally, the contribution of the first fuel assembly (i.e., the m-group fuel assembly) to the fast neutron injection at the target point should not be less than a first preset proportion of the fast neutron injection at the target point, for example, 99%. In addition, the contribution of the second fuel assembly (i.e., the n-group fuel assembly) to the fast neutron injection at the target point should not be less than a second preset proportion of the fast neutron injection at the target point. The first preset proportion and the second preset proportion may be the same or different, for example, the first preset proportion and the second preset proportion may both be 99%. The target point may be the neutron detector in the irradiation monitoring tube, or the injection peak position of the pressure vessel. The distance between the first fuel assembly and the irradiation monitoring tube may be specifically the distance between the first fuel assembly and the neutron detector in the irradiation monitoring tube. The distance between the second fuel assembly and the pressure vessel may be specifically the distance between the second fuel assembly and the injection peak position of the pressure vessel. The first preset value may be determined according to the value of m and the spacing between the fuel assemblies. Similarly, the second preset value may be determined according to the value of n and the spacing between the fuel assemblies.

[0038] The radial power distribution can indicate the position of each fuel assembly in the first reactor and the power of each fuel assembly. After obtaining the radial power distribution of the first reactor and determining the first fuel assembly and the second fuel assembly in the first reactor, the electronic device can obtain the first relative power P of the first fuel assembly in the first reactor based on the radial power distribution of the first reactor, the distribution position of the first fuel assembly in the first reactor, and the distribution position of the second fuel assembly in the first reactor. i , and the second relative power P of the second fuel assembly j .

[0039] Step 102, determining a first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and determining a second contribution share of the second fuel assembly to the fast neutron flux at the peak position of the flux of the pressure vessel.

[0040] Fast neutrons refer to neutrons with higher energy and have higher movement speed in the reactor. Fast neutron flux refers to the number of fast neutrons passing through a unit area per unit time. After determining the first fuel assembly and the second fuel assembly in the first reactor, the electronic device can further determine the first contribution share a of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube.i , and determining a second contribution b of the second fuel assembly to the fast neutron flux at the peak flux position of the pressure vessel j . The peak position of the fluence is the position through which the peak fast neutron fluence passes, which can be determined based on historical data. The peak position of the fluence is usually at a certain circumferential angle of the pressure vessel. The first contribution share refers to the ratio of the contribution of the first fuel assembly to the fast neutron fluence at the target point to the fast neutron fluence at the target point. The second contribution share is the ratio of the contribution of the second fuel assembly to the fast neutron fluence at the target point to the fast neutron fluence at the target point.

[0041] For example, according to the distribution position of the first fuel assembly in the first reactor and the predetermined contribution share of each fuel assembly in the first reactor, the electronic device can determine the first contribution share a of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube. i According to the distribution position of the second fuel assembly in the first reactor and the predetermined contribution share of each fuel assembly in the first reactor, the electronic device can determine the second contribution share b of the second fuel assembly to the fast neutron flux at the peak position of the flux of the pressure vessel. j Alternatively, the first contribution a can be determined by the Monte Carlo method or the conjugate transport method. i and the second contribution share b j .

[0042] Step 103: determining a lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share, and the second contribution share.

[0043] The lead factor represents the ratio of the fast neutron flux at the neutron detector in the irradiation monitoring tube to the maximum fast neutron flux at the inner surface and one-quarter thickness of the pressure vessel. The fast neutron flux is directly proportional to the relative power of the fuel assembly. Based on the above characteristics, after obtaining the first relative power, the second relative power, the first contribution share and the second contribution share, the electronic device can determine the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share and the second contribution share.

[0044] Steps 101 to 103 shown in the embodiment of the present application obtain the first relative power of the first fuel assembly in the first reactor and the second relative power of the second fuel assembly in the first reactor, and determine the first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and determine the second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel, and then determine the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share and the second contribution share. Through the above steps, according to the first relative power, the second relative power, the first contribution share and the second contribution share of the first reactor, the lead factor of the pressure vessel in the first reactor can be simply and quickly determined, reducing the calculation cost of the lead factor.

[0045] In addition, the advance factor can be used as a basis for determining the time to raise the irradiation monitoring tube. Therefore, the method for determining the advance factor of a pressure vessel provided in the embodiment of the present application can improve the efficiency of determining the time to raise the irradiation monitoring tube by reducing the calculation cost when calculating the advance factor.

[0046] In one embodiment of the present application, determining a first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and determining a second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel, comprises:

[0047] Acquiring a composition feature of the first reactor, where the composition feature is used to indicate a reactor type and a reactor structure of the first reactor;

[0048] Matching the composition feature of the first reactor with a plurality of composition features in a preset corresponding relationship to obtain contribution share information corresponding to the composition feature of the first reactor, wherein the corresponding relationship includes contribution share information corresponding to the plurality of composition features and each composition feature, each composition feature in the corresponding relationship is determined according to a second reactor, and the contribution share information corresponding to the composition feature in the corresponding relationship is used to describe the contribution share of each fuel assembly included in the corresponding second reactor;

[0049] Determining the first contribution share based on contribution share information corresponding to the composition characteristics of the first reactor and the distribution position of the first fuel assembly in the first reactor;

[0050] The second contribution share is determined based on the contribution share information corresponding to the composition characteristics of the first reactor and the distribution position of the second fuel assembly in the first reactor.

[0051] First, the electronic device can obtain the composition characteristics of the first reactor, that is, the type and structure of the first reactor. The type of the reactor mainly refers to different types divided according to factors such as fuel form, coolant type, neutron energy distribution, and special design requirements, such as pressurized water reactors, boiling water reactors, high temperature gas-cooled reactors, fast neutron reactors, etc. The reactor structure is the composition and layout inside the reactor. In the embodiment of the present application, the type of the first reactor is a pressurized water reactor. It can be understood that for multiple reactors of the same type, the fuel assemblies are usually selected to be the same. Moreover, for multiple reactors of the same reactor structure, the layout and arrangement of the fuel assemblies are consistent. It can be seen that for multiple reactors of the same type and the same reactor structure, the fuel assemblies in the same distribution position in the multiple reactors contribute the same share to the fast neutron flux at the target point. For example, for Reactor 1 and Reactor 2 of the same type and reactor structure, assuming that fuel assembly 1 in Reactor 1 and fuel assembly 2 in Reactor 2 are in the same distribution position, then fuel assembly 1 and fuel assembly 2 contribute the same share to the fast neutron flux at the target point.

[0052] Therefore, in order to improve the efficiency of subsequently determining the first contribution share and the second contribution share, the electronic device can pre-measure multiple second reactors to obtain a correspondence relationship including the composition characteristics of multiple second reactors and the contribution share information corresponding to each composition characteristic. Each composition characteristic in the correspondence relationship is determined according to a second reactor. The contribution share information corresponding to the composition characteristic in the correspondence relationship is used to indicate the contribution shares corresponding to multiple fuel assemblies in each second reactor. The second reactor refers to a reactor used to determine the correspondence between the composition characteristics and the contribution share information before calculating the lead factor.

[0053] In this way, in the actual application of the method for determining the lead factor of a pressure vessel, the composition characteristics of the first reactor can be matched with the multiple composition characteristics in the corresponding relationship to obtain the contribution share information corresponding to the composition characteristics of the first reactor, and then based on the composition characteristics of the first reactor, the distribution position of the first fuel assembly in the first reactor and the distribution position of the second fuel assembly in the first reactor are determined respectively. Among them, the contribution share information corresponding to the composition characteristics of the first reactor is used to describe the contribution shares corresponding to the multiple fuel assemblies in the first reactor. Subsequently, according to the distribution position of the first fuel assembly in the first reactor and the contribution share information corresponding to the composition characteristics of the first reactor, the first contribution share corresponding to the first fuel assembly can be determined, and according to the distribution position of the second fuel assembly in the first reactor and the contribution share information corresponding to the composition characteristics of the first reactor, the second contribution share corresponding to the second fuel assembly can be determined. In this way, the first contribution share and the second contribution share can be determined, which is convenient for the subsequent calculation of the lead factor.

[0054] In one embodiment of the present application, the corresponding relationship is obtained according to the following process:

[0055] For each of the second reactors, obtaining a composition feature of the second reactor, where the composition feature of the second reactor is used to indicate a reactor type and a reactor structure of the second reactor;

[0056] Determine, based on the composition characteristics of the second reactor, the contribution share of each fuel assembly in the second reactor to the fast neutron flux at a target point, the target point being a neutron detector in an irradiation monitoring tube or a peak position of the flux of a pressure vessel, the contribution share information corresponding to the composition characteristics of the second reactor including the contribution share of each fuel assembly in the second reactor;

[0057] The corresponding relationship is constructed according to the composition characteristics of each of the second reactors and the contribution share information corresponding to the composition characteristics of each of the second reactors.

[0058] In order to improve the efficiency of subsequently determining the first contribution share and the second contribution share, the electronic device can pre-measure multiple second reactors to obtain a corresponding relationship including the composition characteristics of multiple second reactors and the contribution share information corresponding to each composition characteristic. Specifically, for each second reactor, the composition characteristics of the second reactor can be obtained. The composition characteristics of the second reactor are used to indicate the reactor type (for example, a pressurized water reactor) and the reactor structure (such as the arrangement and layout of multiple fuel assemblies) of the second reactor. Then, based on the composition characteristics of the second reactor, the electronic device can determine the contribution share corresponding to each fuel assembly in the second reactor, and further obtain the contribution share information corresponding to the composition characteristics of the second reactor based on the contribution share corresponding to each fuel assembly in the second reactor. In this way, according to the composition characteristics of each second reactor and the contribution share information corresponding to the composition characteristics of each second reactor, a corresponding relationship can be constructed.

[0059] In one embodiment of the present application, determining the contribution of each fuel assembly in the second reactor to the fast neutron flux at the target point based on the composition characteristics of the second reactor includes:

[0060] Based on the composition characteristics of the second reactor, the motion trajectory of each fast neutron emitted by each fuel assembly in the second reactor is simulated to obtain a plurality of transport trajectories, wherein the transport trajectories are used to indicate the trajectory of each fast neutron emitted from the fuel assembly in the second reactor to the target point;

[0061] Determining, based on the plurality of transport trajectories, a contribution of each fuel assembly in the second reactor to the fast neutron flux at the target point;

[0062] respectively determining a first ratio between a contribution of each fuel assembly in the second reactor and a fast neutron flux at the target point;

[0063] The first ratio is determined as the contribution share of the corresponding fuel assembly to obtain the contribution share of each fuel assembly in the second reactor.

[0064] When constructing the corresponding relationship, the electronic device can first determine the contribution share of each fuel assembly in the second reactor. Specifically, the composition characteristics of the second reactor include the reactor type (such as a pressurized water reactor) and the reactor structure (including the position of the irradiation supervision tube, the position of the pressure vessel, the arrangement and layout of multiple fuel assemblies, etc.) of the second reactor. Based on the composition characteristics of the second reactor, the electronic device can use the Monte Carlo method to simulate the forward fast neutron transport process. In other words, based on the composition characteristics of the second reactor, the electronic device can determine the initial state of the fast neutrons (such as position, energy, direction, etc.), as well as the physical properties of the medium (such as density, scattering cross section, absorption cross section, etc.).

[0065] Assuming that each fuel assembly in the second reactor emits fast neutrons uniformly, based on the initial state of the fast neutrons and the physical properties of the medium, using the Monte Carlo method, the electronic device can simulate the motion trajectory of each fast neutron emitted by each fuel assembly in the second reactor, and obtain multiple transport trajectories, that is, the trajectory used to indicate that each fast neutron is emitted from the fuel assembly in the second reactor to the target point. The target point is the neutron detector in the irradiation monitoring tube, or the peak position of the fluence of the pressure vessel. Then, according to each transport trajectory, the electronic device can determine the starting point (that is, a fuel assembly in the second reactor) and the end point (that is, the target point) of each fast neutron, and then determine which fuel assembly in the second reactor the fast neutron received at the target point comes from. In this way, the contribution of each fuel assembly in the second reactor to the fast neutron fluence at the target point can be determined, that is, the number of fast neutrons emitted by each fuel assembly in the second reactor to the target point. Subsequently, the electronic device can respectively determine the first ratio between the contribution of each fuel assembly in the second reactor and the fast neutron fluence at the target point, and determine the first ratio as the contribution share of the corresponding fuel assembly. Through the above-mentioned method, the electronic device can obtain the contribution share of each fuel assembly in the second reactor, and then obtain the contribution share information corresponding to the composition characteristics of the second reactor, so that the corresponding relationship can be established.

[0066] In one embodiment of the present application, determining the contribution of each fuel assembly in the second reactor to the fast neutron flux at the target point based on the composition characteristics of the second reactor includes:

[0067] Using the target point as a neutron source emitting fast neutrons, and based on the composition characteristics of the second reactor, determining the response value of each fuel assembly in the second reactor to the target point;

[0068] determining the sum of the response values ​​of the plurality of fuel assemblies in the second reactor to the target point according to the response values ​​of the fuel assemblies in the second reactor to the target point;

[0069] respectively determining a second ratio of a response value of each fuel assembly in the second reactor to the target point to a sum of response values ​​of multiple fuel assemblies in the second reactor to the target point;

[0070] The second ratio is determined as the contribution share of the corresponding fuel assembly to obtain the contribution share of each fuel assembly in the second reactor.

[0071] When constructing the corresponding relationship, the electronic device can first determine the contribution share of each fuel assembly in the second reactor. The composition characteristics of the second reactor include the reactor type (such as a pressurized water reactor) and the reactor structure (including the position of the irradiation monitoring tube, the position of the pressure vessel, the arrangement and layout of multiple fuel assemblies, etc.) of the second reactor. Based on the composition characteristics of the second reactor, the electronic device can use the conjugate transport method to perform the calculation of the reverse fast neutron transport process. That is to say, according to the composition characteristics of the second reactor, the electronic device can determine the initial state of the fast neutron (such as position, energy, direction, etc.), and the physical properties of the medium (such as density, scattering cross section, absorption cross section, etc.). The target point is the neutron detector in the irradiation monitoring tube, or the peak position of the injection of the pressure vessel. Assuming that the fast neutron is emitted from the target point, then, based on the initial state of the fast neutron and the physical properties of the medium, the electronic device can obtain the response value of each fuel assembly in the second reactor to the target point by using the conjugate transport method for one calculation, and then obtain the sum of the response values ​​of multiple fuel assemblies in the second reactor to the target point according to the response value of each fuel assembly in the second reactor to the target point. In this way, the electronic device can respectively determine the second ratio of the response value of each fuel assembly in the second reactor to the target point and the sum of the response values ​​of multiple fuel assemblies in the second reactor to the target point, and determine the second ratio as the contribution share of the corresponding fuel assembly, thereby obtaining the contribution share of each fuel assembly in the second reactor. In the above manner, the electronic device can obtain the contribution share of each fuel assembly in the second reactor, and then obtain the contribution share information corresponding to the composition characteristics of the second reactor, so that the corresponding relationship can be constructed.

[0072] In one embodiment of the present application, determining the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share, and the second contribution share includes:

[0073] multiplying the first relative power by the first contribution share to obtain a first product;

[0074] multiplying the second relative power by the second contribution to obtain a second product;

[0075] taking the ratio of the first product to the second product as a third ratio;

[0076] The third ratio, the preset correction factor and the preset proportional factor are multiplied together to obtain the lead factor of the pressure vessel.

[0077] According to the first relative power, the second relative power, the first contribution share and the second contribution share, the electronic device can quickly determine the lead factor of the pressure vessel. Specifically, the electronic device can multiply the first relative power by the first contribution share to obtain a first product, and multiply the second relative power by the second contribution share to obtain a second product. The electronic device can determine the ratio of the first product to the second product, and use the ratio as the third ratio, and then multiply the third ratio, a preset correction factor and a preset proportional factor to obtain the lead factor of the pressure vessel. The correction factor can be determined according to the degree of neutron leakage in the core and the axial distribution of neutrons. The proportional factor is a constant and can be obtained according to the type of the first reactor.

[0078] When the first fuel assembly includes multiple fuel assemblies (e.g., fuel assembly 1 and fuel assembly 2), and the second fuel assembly includes multiple fuel assemblies (e.g., fuel assembly 3 and fuel assembly 4), the first relative power P corresponding to fuel assembly 1 may be i1 The first contribution a corresponding to fuel assembly 1 i1 Multiply them to get the first product corresponding to fuel assembly 1, and the first relative power P corresponding to fuel assembly 2 i2 The first contribution a corresponding to fuel assembly 2 i2 Multiply them to obtain the first product corresponding to fuel assembly 2, and then add the first product corresponding to fuel assembly 1 and the first product corresponding to fuel assembly 2 to obtain the sum of the first products. Similarly, the second relative power P corresponding to fuel assembly 3 can be j3 The second contribution b corresponding to fuel assembly 3 j3 Multiply them to get the second product corresponding to fuel assembly 3, and the second relative power P corresponding to fuel assembly 4 j4 The second contribution b corresponding to fuel assembly 4 j4Multiply them to obtain the second product corresponding to fuel assembly 4, and then add the second product corresponding to fuel assembly 3 and the second product corresponding to fuel assembly 4 to obtain the sum of the second products, and then determine the ratio of the sum of the first products to the sum of the second products, and use the ratio as the third ratio, so as to obtain the lead factor of the pressure vessel according to the third ratio, the correction factor and the proportional factor.

[0079] The calculation process of the lead factor of the pressure vessel can satisfy the following formula:

[0080]

[0081] Among them, L f is the leading factor of the pressure vessel, k is the proportional factor, ξ is the correction factor, a i is the first contribution share of the i-th fuel assembly, P i is the first relative power of the i-th fuel assembly, b j is the second contribution share of the jth fuel assembly, P j is the second relative power of the jth fuel assembly, m is the number of first fuel assemblies, and n is the number of second fuel assemblies.

[0082] In this way, by introducing the correction factor, the deviation caused by the difference in the neutron leakage degree and the neutron axial distribution can be corrected, and the obtained advance factor has a higher accuracy.

[0083] Figure 2 is another flow chart of the method for determining the lead factor of a pressure vessel provided in the embodiment of the present application, please refer to Figure 2 The following is an example of a method for determining the lead factor of a pressure vessel provided in an embodiment of the present application. The method for determining the lead factor of a pressure vessel includes:

[0084] Step 201, obtaining radial power distribution of the core of the first reactor;

[0085] Step 202, determining a proportionality factor based on reference data of a unit of the same type having the same reactor structure as the first reactor, and determining a correction factor based on core neutron leakage and neutron axial distribution of the unit of the same type;

[0086] Step 203, determining the first contribution shares of m groups of fuel assemblies near the neutron detectors in the irradiation monitoring tube;

[0087] Step 204, determining the second contribution shares of n groups of fuel assemblies near the injection peak position of the inner wall of the pressure vessel;

[0088] Step 205, determining the first relative power of m groups of fuel assemblies near the neutron detectors in the irradiation monitoring tube according to the radial power distribution, and determining the second relative power of n groups of fuel assemblies near the injection peak position of the inner wall of the pressure vessel;

[0089] Step 206, determining the lead factor of the pressure vessel according to the proportional factor, the correction factor, the first contribution share, the second contribution share, the first relative power, and the second relative power.

[0090] The electronic device can select m groups of fuel assemblies close to the irradiation monitoring tube, and n groups of fuel assemblies close to the circumferential position of the peak position of the pressure vessel. Then, the first contribution a of the selected m groups of fuel assemblies to the fast neutron flux at the neutron detector in the irradiation monitoring tube can be determined. i , and obtain the first relative power P of the m fuel assemblies i , i = 1, ..., m. At the same time, the second contribution share b of the selected n groups of fuel assemblies to the injection peak position of the inner wall of the pressure vessel can be determined j , and obtain the second relative power P of these n fuel assemblies j , j = 1, ..., n. Then, according to formula (1), the lead factor of the pressure vessel can be obtained.

[0091] The 10 groups of lead factor calculation results obtained according to the above-mentioned pressure vessel lead factor determination method are compared with the reference results as shown in Table 1 below.

[0092] Table 1

[0093] Serial number Reference results Lead factor calculation results Relative deviation 1 2.51 2.55 1.55％ 2 3.06 2.94 -3.86％ 3 3.21 3.08 -3.82％ 4 3.06 2.94 -3.97％ 5 2.65 2.53 -4.72％ 6 3.19 3.06 -4.05％ 7 3.34 3.28 -1.72％ 8 2.73 2.66 -2.68％ 9 3.42 3.45 0.87％ 10 3.83 3.73 -2.81％

[0094] It can be seen from the table that the relative deviations of the 10 groups of lead factor calculation results and the reference results are all within ±10%, and the relative deviations are small. Therefore, the lead factor obtained by the pressure vessel lead factor determination method of the embodiment of the present application has a higher accuracy.

[0095] Figure 3 is a schematic diagram of the structure of the pressure vessel lead factor determination device provided in the embodiment of the present application, please refer to Figure 3 The embodiment of the present application further provides a pressure vessel lead factor determination device 300, which can implement the above pressure vessel lead factor determination method, and the device 300 includes:

[0096] The power acquisition module 301 is used to acquire a first relative power of a first fuel assembly in a first reactor and a second relative power of a second fuel assembly in the first reactor, wherein the first fuel assembly is a fuel assembly whose distance from an irradiation monitoring tube is less than a first preset value, and the second fuel assembly is a fuel assembly whose distance from a pressure vessel is less than a second preset value;

[0097] A share determination module 302 is used to determine a first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and to determine a second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel;

[0098] The leading factor determining module 303 is used to determine the leading factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share, and the second contribution share.

[0099] The specific implementation of the pressure vessel lead factor determination device is basically the same as the specific implementation of the pressure vessel lead factor determination method described above, and will not be repeated here.

[0100] The embodiment of the present application also provides an electronic device, the electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the above-mentioned pressure vessel lead factor determination method when executing the computer program. The electronic device can be any smart terminal including a tablet computer, a car computer, etc.

[0101] Figure 4 This is a schematic diagram of the hardware structure of the electronic device provided in the embodiment of the present application. Figure 4 . Electronic equipment includes:

[0102] The processor 401 may be implemented by a general-purpose CPU (Central Processing Unit), a microprocessor, an application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of the present application;

[0103] The memory 402 can be implemented in the form of a read-only memory (ROM), a static storage device, a dynamic storage device, or a random access memory (RAM). The memory 402 can store an operating system and other application programs. When the technical solution provided in the embodiment of this specification is implemented by software or firmware, the relevant program code is stored in the memory 402, and the processor 401 calls and executes the method for determining the lead factor of a pressure vessel in the embodiment of this application;

[0104] Input / output interface 403, used to implement information input and output;

[0105] Communication interface 404, used to realize communication interaction between the device and other devices, which can be realized through wired mode (such as USB, network cable, etc.) or wireless mode (such as mobile network, WI FI, Bluetooth, etc.);

[0106] Bus 405 , which transmits information between various components of the device (e.g., processor 401 , memory 402 , input / output interface 403 , and communication interface 404 );

[0107] The processor 401 , the memory 402 , the input / output interface 403 and the communication interface 404 are connected to each other in communication within the device via the bus 405 .

[0108] An embodiment of the present application further provides a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, the above-mentioned method for determining the lead factor of a pressure vessel is implemented.

[0109] The memory, as a non-transient computer-readable storage medium, can be used to store non-transient software programs and non-transient computer executable programs. In addition, the memory may include a high-speed random access memory, and may also include a non-transient memory, such as at least one disk storage device, a flash memory device, or other non-transient solid-state storage device. In some embodiments, the memory may optionally include a memory remotely disposed relative to the processor, and these remote memories may be connected to the processor via a network. Examples of the above-mentioned network include, but are not limited to, the Internet, an intranet, a local area network, a mobile communication network, and combinations thereof.

[0110] In addition, the embodiments of the present application may be implemented by providing a computer program product. When the instructions in the computer program product are executed by a processor of an electronic device, the electronic device implements any one of the methods for determining the lead factor of a pressure vessel in the above embodiments.

[0111] The method, device, electronic device and storage medium for determining the lead factor of a pressure vessel proposed in the present application obtain the first relative power of the first fuel assembly in the first reactor and the second relative power of the second fuel assembly in the first reactor, and determine the first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and determine the second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel, and then determine the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share and the second contribution share. Through the above steps, according to the first relative power, the second relative power, the first contribution share and the second contribution share of the first reactor, the lead factor of the pressure vessel in the first reactor can be determined simply and quickly, reducing the calculation cost of the lead factor.

[0112] The embodiments described in the embodiments of the present application are intended to more clearly illustrate the technical solutions of the embodiments of the present application and do not constitute a limitation on the technical solutions provided in the embodiments of the present application. Those skilled in the art will appreciate that with the evolution of technology and the emergence of new application scenarios, the technical solutions provided in the embodiments of the present application are also applicable to similar technical problems.

[0113] Those skilled in the art will appreciate that the technical solutions shown in the figures do not constitute a limitation on the embodiments of the present application, and may include more or fewer steps than shown in the figures, or a combination of certain steps, or different steps.

[0114] The device embodiments described above are merely illustrative, and the units described as separate components may or may not be physically separated, that is, they may be located in one place or distributed on multiple network units. Some or all of the modules may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0115] Those skilled in the art will appreciate that all or some of the steps in the methods disclosed above, and the functional modules / units in the systems and devices may be implemented as software, firmware, hardware, or a suitable combination thereof.

[0116] The terms "first", "second", "third", "fourth", etc. (if any) in the specification of the present application and the above-mentioned drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence. It should be understood that the data used in this way can be interchangeable where appropriate, so that the embodiments of the present application described herein can be implemented in an order other than those illustrated or described herein. In addition, the terms "including" and "having" and any of their variations are intended to cover non-exclusive inclusions, for example, a process, method, system, product or device comprising a series of steps or units is not necessarily limited to those steps or units clearly listed, but may include other steps or units that are not clearly listed or inherent to these processes, methods, products or devices.

[0117] It should be understood that in the present application, "at least one (item)" means one or more, and "plurality" means two or more. "And / or" is used to describe the association relationship of associated objects, indicating that three relationships may exist. For example, "A and / or B" can mean: only A exists, only B exists, and A and B exist at the same time, where A and B can be singular or plural. The character " / " generally indicates that the objects associated before and after are in an "or" relationship. "At least one of the following" or similar expressions refers to any combination of these items, including any combination of single or plural items. For example, at least one of a, b or c can mean: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, c can be single or multiple.

[0118] In the several embodiments provided in the present application, it should be understood that the disclosed devices and methods can be implemented in other ways. For example, the device embodiments described above are only schematic. For example, the division of the above units is only a logical function division. There may be other division methods in actual implementation, such as multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the mutual coupling or direct coupling or communication connection shown or discussed can be through some interfaces, indirect coupling or communication connection of devices or units, which can be electrical, mechanical or other forms.

[0119] The units described above as separate components may or may not be physically separated, and the components shown as units may or may not be physical units, that is, they may be located in one place or distributed on multiple network units. Some or all of the units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0120] In addition, each functional unit in each embodiment of the present application may be integrated into one processing unit, or each unit may exist physically separately, or two or more units may be integrated into one unit. The above-mentioned integrated unit may be implemented in the form of hardware or in the form of software functional units.

[0121] If the integrated unit is implemented in the form of a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of the present application is essentially or the part that contributes to the prior art or all or part of the technical solution can be embodied in the form of a software product, and the computer software product is stored in a storage medium, including multiple instructions to enable a computer device (which can be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of various embodiments of the present application. The aforementioned storage medium includes: U disk, mobile hard disk, read-only memory (Read-Only Memory, referred to as ROM), random access memory (Random Access Memory, referred to as RAM), disk or optical disk and other media that can store programs.

[0122] The preferred embodiments of the present invention are described above with reference to the accompanying drawings, but the scope of the rights of the present invention is not limited thereto. Any modification, equivalent substitution and improvement made by a person skilled in the art without departing from the scope and essence of the present invention should be within the scope of the rights of the present invention.

Claims

1. A method for determining the lead factor of a pressure vessel, characterized in that: The method comprises: Obtaining a first relative power of a first fuel assembly in a first reactor and a second relative power of a second fuel assembly in the first reactor, wherein the first fuel assembly is a fuel assembly whose distance from an irradiation monitoring tube is less than a first preset value, and the second fuel assembly is a fuel assembly whose distance from a pressure vessel is less than a second preset value; Determining a first contribution share of the first fuel assembly to the fast neutron flux at a neutron detector in the irradiation monitoring tube, and determining a second contribution share of the second fuel assembly to the fast neutron flux at a peak position of the flux of the pressure vessel; An advance factor of the pressure vessel is determined according to the first relative power, the second relative power, the first contribution share, and the second contribution share.

2. The method according to claim 1, characterized in that The determining of a first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and the determining of a second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel, comprises: Acquiring a composition feature of the first reactor, wherein the composition feature is used to indicate a reactor type and a reactor structure of the first reactor; Matching the composition feature of the first reactor with a plurality of composition features in a preset corresponding relationship to obtain contribution share information corresponding to the composition feature of the first reactor, wherein the corresponding relationship includes contribution share information corresponding to the plurality of composition features and each composition feature, each composition feature in the corresponding relationship is determined according to a second reactor, and the contribution share information corresponding to the composition feature in the corresponding relationship is used to describe the contribution share of each fuel assembly included in the corresponding second reactor; Determining the first contribution share based on contribution share information corresponding to the composition characteristics of the first reactor and the distribution position of the first fuel assembly in the first reactor; The second contribution share is determined based on the contribution share information corresponding to the composition characteristics of the first reactor and the distribution position of the second fuel assembly in the first reactor.

3. The method according to claim 2, characterized in that The corresponding relationship is obtained according to the following process: For each of the second reactors, obtaining a composition feature of the second reactor, where the composition feature of the second reactor is used to indicate a reactor type and a reactor structure of the second reactor; Determine, based on the composition characteristics of the second reactor, the contribution share of each fuel assembly in the second reactor to the fast neutron flux at a target point, the target point being a neutron detector in an irradiation monitoring tube or a peak position of the flux of a pressure vessel, the contribution share information corresponding to the composition characteristics of the second reactor including the contribution share of each fuel assembly in the second reactor; The corresponding relationship is constructed according to the composition characteristics of each of the second reactors and the contribution share information corresponding to the composition characteristics of each of the second reactors.

4. The method according to claim 3, characterized in that The determining, based on the composition characteristics of the second reactor, the contribution of each fuel assembly in the second reactor to the fast neutron flux at the target point comprises: Based on the composition characteristics of the second reactor, the motion trajectory of each fast neutron emitted by each fuel assembly in the second reactor is simulated to obtain a plurality of transport trajectories, wherein the transport trajectories are used to indicate the trajectory of each fast neutron emitted from the fuel assembly in the second reactor to the target point; Determining, based on the plurality of transport trajectories, a contribution of each fuel assembly in the second reactor to the fast neutron flux at the target point; respectively determining a first ratio between a contribution of each fuel assembly in the second reactor and a fast neutron flux at the target point; The first ratio is determined as the contribution share of the corresponding fuel assembly to obtain the contribution share of each fuel assembly in the second reactor.

5. The method according to claim 3, characterized in that: The determining, based on the composition characteristics of the second reactor, the contribution of each fuel assembly in the second reactor to the fast neutron flux at the target point comprises: Using the target point as a neutron source emitting fast neutrons, and based on the composition characteristics of the second reactor, determining the response value of each fuel assembly in the second reactor to the target point; determining the sum of the response values ​​of the plurality of fuel assemblies in the second reactor to the target point according to the response values ​​of the fuel assemblies in the second reactor to the target point; respectively determining a second ratio of a response value of each fuel assembly in the second reactor to the target point to a sum of response values ​​of multiple fuel assemblies in the second reactor to the target point; The second ratio is determined as the contribution share of the corresponding fuel assembly to obtain the contribution share of each fuel assembly in the second reactor.

6. The method according to claim 1, characterized in that The step of determining the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share, and the second contribution share comprises: multiplying the first relative power by the first contribution share to obtain a first product; multiplying the second relative power by the second contribution to obtain a second product; taking the ratio of the first product to the second product as a third ratio; The third ratio, the preset correction factor and the preset proportional factor are multiplied together to obtain the lead factor of the pressure vessel.

7. A device for determining an advance factor of a pressure vessel, characterized in that: The device comprises: a power acquisition module, used for acquiring a first relative power of a first fuel assembly in a first reactor, and a second relative power of a second fuel assembly in the first reactor, wherein the first fuel assembly is a fuel assembly whose distance from an irradiation monitoring tube is less than a first preset value, and the second fuel assembly is a fuel assembly whose distance from a pressure vessel is less than a second preset value; a share determination module, configured to determine a first contribution share of the first fuel assembly to the fast neutron flux at the neutron detector in the irradiation monitoring tube, and to determine a second contribution share of the second fuel assembly to the fast neutron flux at the flux peak position of the pressure vessel; An advance factor determination module is used to determine the lead factor of the pressure vessel according to the first relative power, the second relative power, the first contribution share, and the second contribution share.

8. An electronic device, characterized in that: The electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the method for determining the lead factor of a pressure vessel according to any one of claims 1 to 6 when executing the computer program.

9. A computer-readable storage medium storing a computer program, characterized in that: When the computer program is executed by a processor, the method for determining the lead factor of a pressure vessel according to any one of claims 1 to 6 is implemented.

10. A computer program product, characterized in that When the instructions in the computer program product are executed by the processor of the electronic device according to claim 8, the electronic device executes the method for determining the lead factor of a pressure vessel according to any one of claims 1 to 6.

Images